Abstract: A motor operated valve diagnostic data acquisition system including: a motor operated valve assembly; a transmitter, the transmitter being permanently connected in a housing of a motor operated valve assembly; a receiver, the transmitter transmitting signals to the receiver via motor operated valve cables, the cables being existing motor operated valve cables; and electronic circuitry connected to the receiver, the electronic circuitry processing the signals received by the receiver.

Abstract: The invention is principally directed to a reduced order model, XEDOR, facilitating the prediction of and the diagnostics of pellet-clad interaction stress-corrosion-cracking failure of nuclear fuel rods. The invention more particularly relates to assessment of susceptibility to PCI failure for guidance in the design of fuel loading in nuclear reactors. The invention additionally relates to the protection against PCI failure by providing operational information to operators of a nuclear reactor during power maneuvering, including predictive calculations prior to executing power maneuvers. Additionally, the invention relates to the diagnostics of an event suggesting a possible PCI cladding failure.

Abstract: A nuclear fuel assembly spacer grid defining a lattice of cells for receiving fuel rods is provided. The spacer grid includes a peripheral band composed of at least one peripheral strip delimiting a portion of the peripheral contour of the spacer grid, and at least one spacer grid positioning spring elastically deformable and formed in the peripheral band.

Abstract: A method for recycling AgInCd control rod absorber bar material from a used control rod from a nuclear power plant includes sectioning AgInCd absorber bar from a used control rod into a first section and a second section, the first section having a higher radioactivity than the second section; and recycling the material of the second section of the AgInCd absorber bar.

Abstract: A gland member within a medical valve is configured to have a substantially consistent or enlarging internal volume as the valve transitions from a closed mode to an open mode. The valve has a housing forming an interior containing a flow path, and a stationary post member within the interior. The post member has a lumen that is a part of the flow path. The lumen has an opening to the interior of the housing. The valve further includes a gland member circumscribing the post member to produce a variable volume region formed at least in part between the gland member itself and the post member. The variable volume region is a part of the flow path, while the gland member occludes the post lumen opening when in the closed mode. The variable volume region has an open volume that is no less than its closed volume.

Abstract: A method for determining tube support plate blockage of a steam generator includes the following steps: measuring at least five different eddy current values per tube support intersection; calculating a nominal clean fit radius of flow hole; determining a center signal response; converting the center signal response to a deposit thickness; determine an edge reduction; converting the edge reduction to an edge thickness; calculating the resulting flow hole radius; verifying the reasonableness of the resulting flow hole radius; and determining a virtual calibration range.

Abstract: A method for chemical decontamination of an oxide-coated surface of a metal structural part or of a system in a nuclear power plant with several cleaning cycles, involves oxidation steps, in which the oxide layer is treated with an aqueous solution containing an oxidation agent, and a subsequent decontamination step, in which the oxide layer is treated with an aqueous solution of an acid. At least one oxidation step is carried out in an acid solution and at least one oxidation step in an alkaline solution.

Abstract: A protective cover is provided for a ventilation opening in a plant space of a nuclear-engineering plant. The cover is configured, with a construction that is simple, and with simple manufacture and mounting, for a sufficient air-flow cross section and also for protection against ingress of destructive projectiles into the building interior. The protective cover has profile elements, which are arranged in a mounting plane in a rectangular frame, are aligned in a longitudinal direction such that they are parallel to one another, and are shaped in the same way and orientated in the same way. The relevant profile element has an L-shaped or V-shaped cross section with two limbs that meet in a peak, with the peaks pointing in the transverse direction. A spacing between profile elements that immediately follow each other is chosen such that there is no rectilinear passage between them.

Abstract: An assembly is provided that includes at least one first conduit and at least one second conduit connected together through a connecting device. The connecting device includes an exteriorly threaded tube; a connecting part attached to one end of the tube and including an orifice; a holding nut screwed onto the tube and axially maintaining the connecting part relative to a tube; and a retaining member attached on the holding nut and engaging with the first conduit so as to axially retain the first conduit fitted into the orifice, the retaining member cooperating with the first conduit so as to oppose the unscrewing of the holding nut.

Abstract: A method for controlling the positions of a plurality of nuclear fuel assemblies (1) relative to an upper core plate (3) in a nuclear reactor core, the method including the following steps: choosing a reference point (13) in internals or in a reactor vessel; determining the positions of S-shaped holes of the nuclear fuel assemblies (1) relative to the reference point (13), each S-shaped hole being intended to cooperate with a corresponding centering pin of the upper core plate (3); acquiring the positions of the centering pins of the upper core plate (3) relative to the reference point (13); and comparing the positions of the S-shaped holes and the positions of the pins and deducing therefrom whether the nuclear fuel assemblies (1) are correctly positioned relative to the upper core plate (3).

Abstract: A component for conducting or receiving a fluid, in particular a component of a fluid-conducting line system of an industrial plant, especially of a line system of a tertiary cooling circuit of a nuclear power plant, includes a wall having a supporting structure made of a glass-fiber-reinforced plastic. Electrically insulating inner and outer protective layers are disposed on respective inner and outer surfaces of the supporting structure. An electrically conductive inner intermediate layer lies between the inner protective layer and the supporting structure and is provided with an electrical terminal. An electrically conductive outer intermediate layer lies between the outer protective layer and the supporting structure, is provided with an electrical terminal and is electrically insulated from the inner intermediate layer. A method for testing the component is also provided.

Abstract: A method and a device depressurize a nuclear power plant. A depressurization flow is conducted out of a containment shell into the atmosphere via a depressurization line having a filter system. The filter system contains a filter chamber having an inlet, an outlet, and a sorbent filter. The depressurization flow is first conducted in a high-pressure section, then is depressurized by expansion at a throttle device, then conducted through the filter chamber having the sorbent filter, and finally blown out. To enable an effective retention of activity carriers contained in the depressurization flow, including organic compounds containing iodine, the depressurization flow depressurized by the throttle device is conducted through a superheating section before the depressurization flow enters the filter chamber, in which superheating section the depressurization flow is heated from the not yet depressurized depressurization flow to a temperature that is at least 10 ° C. above the dew point temperature.

Abstract: In a process for estimating the concentration (C) of a chemical element in the primary coolant of a nuclear reactor, a dilution solution or a concentrated solution of said chemical element in a predetermined concentration (C*) is injected into the primary coolant within the reactor, and the reactor includes a sensor capable of measuring a quantity (Cm) representing the concentration of said chemical element. The process is an iterative process in which repeatedly in each time step k: a stage of acquiring quantities (qdk) and (qck) representing the injected flows of dilution solution and concentrated solution in step k, and a quantity (Cmk) representing the concentration measured by the sensor; a stage of calculating an estimated value (Cek+1) of the concentration of said chemical element in the primary coolant in step k+1 on the basis of representative quantities (qdk, qck, Cmk) acquired in stage k.

Abstract: The invention relates to a method of determining at least one technological uncertainty factor in respect of nuclear fuel elements (23) as a function of variations in the production parameters of the elements (23) in relation to nominal values. The inventive method comprises a step involving the use, for at least one production parameter, of a collective variation in said parameter in relation to the nominal value within a batch of produced elements (23). The invention can be used, for example, to design, produce and check pellets for light water reactors.

Abstract: A device for the dry handling of nuclear fuel assemblies is provided. The device includes a transfer basket which can be connected to a lifter and which includes a gripper for gripping the fuel assembly to be transferred, the gripper being supported by a lift built into the basket; and an indexing table which can be placed on a cask and which comprises a positioner for positioning the basket over a slot in the cask.

Abstract: A garment, such a jacket or pair of pants, affords protection from ballistic impacts. The garment comprises at least two tubular sections of strong fabric, the sections overlapping such that said sections can telescope to allow flexing of a body part enclosed thereby without exposing any part of the body part. A set of protective clothing comprises the ballistic protective garment and an outer garment of heat and blast protective material.

Abstract: An armor panel assembly may comprise a set of bolts for attaching to a vehicle hull, an inner panel demountably attached to the bolts, and at least one outer panel demountably attached to the inner panel. The assembly may include a support panel for attaching the bolts to the hull and may further include brackets for mounting the support panel to the hull. Further, a kit of parts for forming a vehicle armor panel assembly may comprise a set of bolts for attaching to a vehicle hull, an inner panel demountably attachable to the bolts, and at least one outer panel demountably attachable to the inner panel.

Abstract: An assembly is provided including a mobile structure including a main pipe equipped with a first end intended to be connected to a water supply and a second end intended to be connected to a circuit connected to the primary circuit of the reactor, and including between these two ends in the direction of circulation of the water, a pump, a water heating device, an injector for continuously injecting the powdered neutron-absorbing element into the water of the main pipe, a first mixer for mixing and dissolving powder with water and a controller driving and controlling the flow rate of the water and the flow rate of the powder injected.

Abstract: A nuclear fuel assembly is provided for a boiling water reactor. The nuclear fuel assembly includes a base, a head, and a bundle of full length fuel rods and partial length fuel rods, said bundle extending upwardly and longitudinally from the base to the head. The nuclear fuel assembly includes at least one clamp for longitudinally retaining a lower plug of a partial length fuel rod with respect to the base. The clamp is an additional part fitted to the base, the clamp is at least partially received in a housing provided in the base, and the clamp is assembled to the base by mechanical engagement of complementary assemblies.

Abstract: A method takes a sample of a deposit on a secondary side of a pipe base plate of a steam generator of a nuclear power plant, In the method a steam generator pipe is removed from the pipe base plate to expose a hot pipe bore penetrating the pipe base plate. A removal tool of a device for taking the sample is introduced into the hot pipe bore by the primary side of the pipe base plate which is opposite the secondary side. A part of the deposit is removed by the removal tool as the sample. The sample is transported and removed from the steam generator. The removal tool is removed from the steam generator. The device contains the removal tool which can be introduced by a primary side of the pipe base plate in an exposed hot pipe bore penetrating the pipe base plate for removing the sample.